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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
2020 ANS Virtual Winter Meeting
November 16–19, 2020
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U.S. reactor technologies to be featured at IAEA conference
A virtual side event at the 64th General Conference of the International Atomic Energy Agency will spotlight U.S. reactor technologies. The free event, US Reactor Technologies: Flexible Energy Security for Real-World Challenges, will be held this Thursday, September 24, from 9:00 a.m. to 10:30 a.m. (EDT).
The event will highlight the capabilities of small modular reactors and other innovative reactors for addressing countries’ current needs. It will also examine anticipated challenges in the future, as well as underscore the need to act now.
The event is sponsored by the U.S. Department of Energy’s Office of Nuclear Energy. Advanced registration is required.
Soon K. Lee, Maolong Liu, Nicholas R. Brown, Kurt A. Terrani, Youho Lee
Nuclear Technology | Volume 206 | Number 2 | February 2020 | Pages 339-346
Technical Paper | dx.doi.org/10.1080/00295450.2019.1670010
Articles are hosted by Taylor and Francis Online.
Steady-state internal flow boiling experiments were conducted on various materials, including accident tolerant fuel cladding material Fe–12Cr–6Al (C26M2) alloy, Zircaloy, and metal-based materials, at atmospheric pressure (84 kPa), 10°C inlet subcooling, and 200 kg/m2‧s mass flow entering the test tubes until critical heat flux (CHF) was reached. The clad thickness effects on flow boiling CHF were evaluated showing a negative relation between CHF and clad thickness up to 0.711 mm. An approach was established to mechanistically understand the measured CHF differences among the tested materials using thermal effusivity, activity, diffusivity, and surface thermal economy. No clear relations were observed within the range of thermal properties of the tested materials. Compared to past CHF data for a mass flux of 300 kg/m2‧s, the CHF data for 200 kg/m2‧s showed increased relative differences among materials. This result implies that higher mass flux may further decrease apparent material sensitivity to CHF.